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Preliminary accident analysis of the loss of vacuum in vacuum vessel for the European DEMO HCPB blanket concept

Jin, Xue Zhou 1; Raskob, Wolfgang 2
1 Institut für Neutronenphysik und Reaktortechnik (INR), Karlsruher Institut für Technologie (KIT)
2 Institut für Thermische Energietechnik und Sicherheit (ITES), Karlsruher Institut für Technologie (KIT)

Abstract:

Design basis accidents are investigated continuously for the European DEMO reactor accompanying its development. One selected postulated initial event (PIE) is a loss of vacuum (LOVA) in vacuum vessel (VV) with large ingress of air induced by rupture in a VV penetration. It has been investigated for the helium cooled pebble bed (HCPB) blanket concept according to the DEMO baseline 2017. The associated primary heat transfer system (PHTS) and the related systems in the tokamak building, from the VV to the PHTS vault and galleries, are considered for the investigation. The LOVA is postulated to occur at a port seal of the electron cyclotron equatorial port plug on the side of the closure plate with (i) a small leak of 1.0 × 10−3 m2, or (ii) a large break size of 1.0 × 10−2 m2. Air ingress from one port cell into the VV leads to the VV pressurization and the fusion power termination followed by an unmitigated plasma disruption. A loss of off-site power for 32 h is assumed to coincide with the disruption. An in-vessel loss of coolant accident (LOCA) is considered as a consequence if the affected first wall (FW) reaches the defined temperature of 1000 °C. ... mehr


Verlagsausgabe §
DOI: 10.5445/IR/1000170074
Veröffentlicht am 26.04.2024
Originalveröffentlichung
DOI: 10.1088/1741-4326/ad383b
Scopus
Zitationen: 1
Dimensions
Zitationen: 1
Cover der Publikation
Zugehörige Institution(en) am KIT Institut für Neutronenphysik und Reaktortechnik (INR)
Institut für Thermische Energietechnik und Sicherheit (ITES)
Publikationstyp Zeitschriftenaufsatz
Publikationsdatum 01.05.2024
Sprache Englisch
Identifikator ISSN: 0029-5515, 1741-4326
KITopen-ID: 1000170074
HGF-Programm 31.13.06 (POF IV, LK 01) Plant Engineering
Erschienen in Nuclear Fusion
Verlag International Atomic Energy Agency (IAEA)
Band 64
Heft 5
Seiten Art.-Nr.: 056038
Vorab online veröffentlicht am 12.04.2024
Nachgewiesen in Web of Science
Dimensions
Scopus
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